DONES中子源监测模块-技术挑战

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-04-30 DOI:10.1016/j.fusengdes.2025.115125

U. Wiącek , S. Becerril , J. Castellanos , K. Dojko , W. Janik , R. Kantor , J. Kotuła , A. Kulińska , A. Kurowski , R. Ortwein , M. Turzański

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引用次数: 0

摘要

启动监测模块（STUMM）将用于在IFMIF-DONES（国际聚变材料辐照设施- DEMOOriented中子源）调试阶段表征中子和伽马辐射场。STUMM将放置在中子源后面，在为材料样品的辐照预留的空间中。该模块的主要任务是表征中子源和辐照参数，对仪器进行鉴定，并验证理论计算。为了完成这一任务，计划为STUMM配备约240个不同的探测器，这些探测器分布在钻井平台上。由于其复杂性、非常苛刻的操作条件以及模块的独一无二的应用，STUMM的工程设计是一项具有挑战性的任务。这项工作介绍了STUMM的工程设计，包括对模块的主要目标、要求、几何形状和提出的工程解决方案的描述。

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STUMM – monitoring module for DONES neutron source – technical challenges

The Start-Up Monitoring Module (STUMM) will be used to characterize the neutron and gamma radiation fields during the commissioning phase of IFMIF-DONES (International Fusion Materials Irradiation Facility — DEMOOriented Neutron Source). STUMM will be placed behind the neutron source in the space reserved for the irradiation of material samples. The main mission of the module is to characterize the neutron source and irradiation parameters, qualify the instrumentation, and validate the theoretical calculations. To achieve this mission, it is planned to equip STUMM with about 240 various detectors arranged in rigs. The engineering design of STUMM is a challenging task due to its complexity, very harsh operating conditions, and one-of-a-kind application of the module. This work presents the engineering design of STUMM, including a description of the module's main objective, its requirements, the geometry, and the proposed engineering solutions.

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.